Monte Carlo Modeling of Delayed Neutrons from Photofission

We describe the implementation of algorithms related to the delayed neutron production in photon-induced fission on actinides. The algorithms are based on data from experiments and have been implemented in the MCNP-PoliMi code. The modified code is being used to design and analyze methods to identify concealed highly enriched uranium with a system based on the use of photon interrogation and scintillation detectors.